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Non-Intrusive Velocity Measurements with MTV During DCC Event in the HTTFVelocity profiles are measured using molecular tagging velocimetry (MTV) in the high temperature test facility (HTTF) at Oregon State University during a depressurized conduction cooldown (DCC) event. The HTTF is a quarter scale electrically heated nuclear reactor simulator designed to replicate various accident scenarios. During a DCC, a double ended guillotine break results in the reactor pressure vessel (RPV) depressurizing into the reactor cavity and ultimately leading to air ingress in the reactor core (lock-exchange and gas diffusion). It is critical to understand the resulting buoyancy-driven flow to characterize the reactor self-cooling capacity through natural circulation. During tests conducted at ambient pressure and temperature, the RPV containing helium is opened (via the hot and cold legs) to a large vessel filled with nitrogen to simulate the atmosphere. The velocity profile on the hot leg pipe centerline is recorded at 10 Hz with MTV based on NO tracers. The precision of the velocimetry was measured to be 0.02 m/s in quiescent flow prior to the tests. A helium flow from the RPV is initially observed in the top quarter of the pipe. During the first 20 seconds of the event, helium flows out of the RPV with a maximum velocity below 2 m/s. The velocity profile transitions from parabolic to linear in character and decays slowly over the rest of the recording; peak velocities of 0.2 m/s are observed after 30 min. A counter-flow of nitrogen is also observed intermittently, which occurs at lower velocities (>0.1 m/s).
Document ID
20170009119
Acquisition Source
Langley Research Center
Document Type
Conference Paper
Authors
Andre, M. A.
(George Washington Univ. Washington, DC, United States)
Bardet, P. M.
(George Washington Univ. Washington, DC, United States)
Cadell, S. R.
(Oregon State Univ. Corvallis, OR, United States)
Woods, B.
(Oregon State Univ. Corvallis, OR, United States)
Burns, R. A.
(National Inst. of Aerospace Hampton, VA, United States)
Danehy, P. M.
(NASA Langley Research Center Hampton, VA, United States)
Date Acquired
September 27, 2017
Publication Date
September 3, 2017
Subject Category
Fluid Mechanics And Thermodynamics
Report/Patent Number
NF1676L-26169
Meeting Information
Meeting: International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17)
Location: Xian
Country: China
Start Date: September 3, 2017
End Date: September 8, 2017
Sponsors: American Nuclear Society
Funding Number(s)
WBS: WBS 295670.01.07
Distribution Limits
Public
Copyright
Public Use Permitted.
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